ML19317F819
| ML19317F819 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 01/09/1975 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19317F820 | List: |
| References | |
| NUDOCS 8002210573 | |
| Download: ML19317F819 (2) | |
Text
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%' ~') SACRAMENTO MUNICIPAL UTILITY DIST G5UD 1708 59th Street. Box 15830. Sacramento. Cahfornia 95813.(916)452 3211 January 9, 1975 i:
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Re: Operating License DPR-54 Docket No. 50-312 Abnormal Occurrence A0-50-312-74-14
Dear Sir:
As defined by Technical Specifications for the Rancho Seco N'uclear.
'v Power Station, Section 6.12.2B, we are reporting the following abnormal occurrence as A0-74-14.
1 During a routine surveillance inside the Reactor Building using a (A) television camera, a 24 ft. aluminum ladder was observed inside the secondary i
\\j rhiel'. mccr the Wrth enaa-rhermoh at eam generator. The reactor was subse-quently shut down, and the ladder was removed from the Reactor Building. An investigation revealed that the ladder had been left over from the initial' construction activities.
The FSAR Section 14-C limits the quantity of aluminum in the Reactor ".
Building to 500 lbs. The exact quantity in the building is normally 537.6 lbs.'
of which 94.6 lbs. is coated and not exposed to the corrosive environment of; NaOH following LOCA. This would leave 443 lbs. of aluminum in the building and a 57 lb. cntgin. A 24 ft. standard duty-ladder weighs 36 lbs. which, during the initial discovery December 7, did not. necessitate immediate action since the maximum aluminum was not exceeded.
'l On January 7, 1975 it was determined that an additional ladder was in the Reactor Building. The ladder was removed that same day and an inspection
-~ l of the building was conducted to assure that no other aluminun had been lef t over from construction. The only additional item located was an aluminum
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. chair that also was removed.
5' The total accountability for all items of aluminum prior to December 7, 1974, may have been about 521 lbs. which includes the 443 lbs. allowed, two 24 ft. aluminum ladders and a chair.
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. Director Directorate of Licensing January 9, 1975 i
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1 The inspection conducted January 7, 1975 assures that the present quantity of aluminum in the Reactor Building is less than calculated in the d
FSAR for hydrogen generation following LOCA.
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The Plant Review Committee determined that during subsequent operations this will be' prevented.by the controlled " Tool List" which logs all tools and equipment entering the Reactor Building.
There was no plant, transient associated with this occurrence.
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